|
|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20235S2441989-02-16016 February 1989
Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels
ML20237C6781987-11-30030 November 1987
Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc
ML20236W2731987-11-23023 November 1987
Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run
ML20236X0081987-11-18018 November 1987
Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled
ML20236Y2151987-05-15015 May 1987
Special Rept 87-02:on 870216,reactor Manually Scrammed Due to Erroneous Indication of Low Voltage on Turbine Bldg MCC1A.On 870406,reactor Power Dropped Following Trip of 1A Forced Circulation Pump
ML20211E4971986-06-0404 June 1986
Special Rept 86-02:on 860307 & 0525,thermal Power Changed by Greater than 15% of Rated Thermal Power within 1 H on Three Occasions.Caused by Bus 1B Power Loss,Reactor Forced Circulation Pump Trip & Control Air Sys
ML20138B7861986-03-11011 March 1986
Special Rept:On 860311,internal Portion of High Pressure Svc Water Sys Which Supplies Fire Suppression Sys Removed from Svc to Replace Valve Required to Be Tested by Inservice Testing Program
ML20141P1241986-03-0606 March 1986
Incident Rept DPC-86-1:on 860104,seal Inject Supply Line Separated at Swagelock Fitting,Spraying Water & Resulting in Reactor Shutdown.Cause Unknown.Mechanical Seal on CRD 2 Reworked
ML20138L8431985-10-21021 October 1985
Special Rept 85-02:on 850725,0909 & 14,reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H. Power History,Fuel Burnup,Cleanup Flow History,Offgas Activity Levels & Gross Alpha Activity Levels Discussed
ML20138L7451985-10-0808 October 1985
Special Rept:Discusses Circumstances Which Led to Inaccuracies in Personnel Cumulative Lifetime Dose Records. Cumulative Permanent Doses in Radiation Dosimetry Rept Do Not Agree W/Records Maintained in Computer File
ML20128N9141985-07-18018 July 1985
Special Rept 85-01:providing Results of Sampling & Analysis Actions & Addl Operational Info for Six Occasions When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H
ML20062D1601982-07-26026 July 1982
Ro:On 820726,internal Portion of Fire Suppression Water Sys Removed from Svc in Order to Replace Fire Hose Cabinets Rendering Fire Suppression Water Sys Inoperable.Backup Capability Provided
ML20054F1711982-06-0707 June 1982
RO 82-14:on 820605,w/reactor in Operating Condition 2 at 50 X 10-6% Power,Review of Shift Supervisor Log Revealed Primary Water Alpha Activity of 7.46 X 10-6 Uci/Gm.Reactor Shutdown Conducted 820605 in Accordance W/Tech Spec
1989-02-16
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210A6361999-04-30030 April 1999
Rev 13 to Quality Assurance Program Description
ML20206J3751999-04-29029 April 1999
Rev 13 to QA Program Description
ML20207A9591999-01-31031 January 1999
Revised LACBWR Decommissioning Plan
ML20196G0751998-12-31031 December 1998
1998 Annual Rept for Dairyland Power Cooperative
ML20204D8371998-12-31031 December 1998
Annual Rept for 1998 - Rept of Changes,Tests & Experiments for Lacbwr. with
ML20237E2701998-07-31031 July 1998
Rev 12 to QA Program Description
ML20196A9241998-07-31031 July 1998
Rev 12 to LACBWR QA Program Description (Qapd)
ML20202J0691998-01-31031 January 1998
Revised LACBWR Decommissioning Plan
ML20202J0781998-01-31031 January 1998
Revised LACBWR Initial Site Characterization Survey for Safstor
ML20203K0041997-12-31031 December 1997
Annual Operating Rept for 1997 - Rept of Changes,Tests & Experiments
ML20249B7101997-12-31031 December 1997
Navigating for Our Future Dairyland Power 1997 Annual Rept. W/O Ltr
ML20138B7771997-04-25025 April 1997
Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License
ML20137R7731997-04-11011 April 1997
Safety Evaluation Approving Changes to QAP Description
ML20149K2071996-12-31031 December 1996
Conquering New Frontiers,Dairyland Power Cooperative 1996 Annual Rept
ML20135C3901996-12-31031 December 1996
Annual Rept for 1996 - Rept of Changes,Tests & Experiments
ML20132F8721996-10-31031 October 1996
Revised LACBWR Decommissioning Plan
ML20134M2531996-02-20020 February 1996
Revised Rev 11 to QA Program Description
ML18012A9001995-12-31031 December 1995
Annual Rept - 1995 of Changes,Tests & Experiments. W/ 960220 Ltr
ML18011B1461995-04-20020 April 1995
LER 95-001-00:on 950417,noted That HPSW to Containment Building Isolated.Caused by Momentary LOP Due to Operational Test of 1A Edg.Procedures for Test Being Modified to Include Instructions to Verify Value Being open.W/950420 Ltr
ML20056E2631993-08-10010 August 1993
LACBWR Containment Bldg Structural Analysis. W/One Oversize Drawing
ML20056E2621993-07-31031 July 1993
Nonproprietary Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve
ML20127D3901993-01-13013 January 1993
SE Supporting Amend 67 to License DPR-45
ML20128K6011992-12-31031 December 1992
Corrected App a Re Std Format for Reporting Number of Personnel & man-rem by Work & Job Function,To Annual Rept for 1992 - Rept of Changes,Tests & Experiments
ML20128D3421992-12-31031 December 1992
LACBWR Annual Rept 1992
ML20062B4761990-09-30030 September 1990
Monthly Operating Rept for Sept 1990 for LACBWR
ML20248D0941989-08-31031 August 1989
Monthly Operating Rept for Aug 1989 for LACBWR
ML20245G6571989-07-31031 July 1989
Monthly Operating Rept for Jul 1989 for LACBWR
ML20245F9681989-06-30030 June 1989
Monthly Operating Rept for June 1989 for LACBWR
ML20245J7351989-04-26026 April 1989
Safety Evaluation Supporting Amend 65 to License DPR-45
ML20245F8241989-02-28028 February 1989
Monthly Operating Rept for Feb 1989 for La Crosse Bwr.W/
ML20235S2441989-02-16016 February 1989
Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels
ML20245F7771989-01-31031 January 1989
Monthly Operating Rept for Jan 1989 for LACBWR
ML20246H8771988-12-31031 December 1988
1988 Dairyland Power Cooperative Annual Rept
ML20205T1271988-10-31031 October 1988
Monthly Operating Rept for Oct 1988 for La Crosse Bwr.W/
ML20151T0991988-08-0808 August 1988
Safety Evaluation Supporting Approval of Util Rev 10 to Emergency Plan
ML20150D7051988-07-0808 July 1988
Safety Evaluation Supporting Rev 10 to Emergency Plan
ML20155F9161988-05-31031 May 1988
Safety Evaluation Supporting Amend 62 to License DPR-45
ML20151G0591988-04-11011 April 1988
Safety Evaluation Supporting Amend 60 to Provisional License DPR-45
ML20148C3941988-03-15015 March 1988
Safety Evaluation Supporting Amend 59 to License DPR-45
ML20149G0711988-01-0404 January 1988
Safety Evaluation Supporting Amend 58 to License DPR-45
ML20147A9731987-12-31031 December 1987
Decommissioning Plan
ML20149J3441987-12-31031 December 1987
LACBWR Annual Rept 1987
ML20195D7811987-12-31031 December 1987
1987 Dairyland Power Cooperative Annual Rept
ML20237C6781987-11-30030 November 1987
Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc
ML20236W2731987-11-23023 November 1987
Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run
ML20236X0081987-11-18018 November 1987
Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled
ML20234C3931987-10-20020 October 1987
Rev 5 to QA Program Description
ML20151B2351987-10-20020 October 1987
Revised Rev 5 to QA Program Description
ML20235R0531987-09-30030 September 1987
Determination of Potential Radiological Consequences to Members of Public from Fuel Handling Accident at La Crosse Nuclear Facility
ML20235B5711987-09-15015 September 1987
Safety Evaluation Supporting Amend 57 to License DPR-45
1999-04-30
[Table view] |
Text
- _-_
9 C.,b D DA/RYLAND hb[M[ COOPERATIVE
- PO. BOX 817 LA CRO (608) 788-4000 JAMES W. TAYLOR General Manager MIORITYROUTIE February 16, 1989 pg In reply, please ' FvEr ---
{fd5 "#
refer to LAC-12701 n ,
4 1 DOCKET NO. 50-409 Mr. A. Bert Davis, Regional Administrator Directorate of Regulatory Operations U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Davis:
SUBJECT:
Dairyland Power Cooperative (DPC)
La Crosse Boiling Water Reactor (LACBWR)
Provisional License No. DPR-45 Special Report Supplement
REFERENCES:
- 1) LACBWR Technical Specifications Section 4.2.18.1
- 2) LACBWR Technical Specifications Section 6.9.2
- 3) DPC Letter, Taylor to Davis, LAC-12465, dated January 4, 1988 The letter of Reference 3 6. tailed the events leading to a declaration of INOPERABILITY of the 1B High Pressure Service Water diesel. The 30-day i
time period allowed to submit the Special Report required by Reference 1 expired before the cause of the failure could be identified and the diesel declared operable again. This necessitated a supplement to the Special Report submitted in the letter of Reference 3. This letter constitutes that supplement.
In the days and weeks following the failure of the IB fire pump diesel, extensive testing and engineering analyses were performed. The conclusion drawn was that the fuel supply system was the source of the problem. The tests and analyses that were performed included the following:
- 1. Fuel lines were blown out.
- 2. Fuel filters were inspected and changed.
/
,( A 8903070036 890216 g PDR ADOCK 05000409P DL. ,,-
S FEB 2 2199g
Mr. A. Bert Davis
, LAC-12701 Page 2 February 16, 1989
- 3. Check valves were inspected.
- 4. Contents of the fuel supply tank were filtered.
- 5. Fuel lines on the engine were replaced.
- 6. Temporary gauges were installed to monitor fuel supply line vacuum and fuel pump discharge pressure.
- 7. Fuel supply tank was emptied and refilled.
- 8. Fuel sample was obtained and analyzed by an outside agency.
- 9. Fuel was diluted to an approximate 50/50 mixture of #1 and #2 diesel fuel.
- 10. Injection pump was sent to pump service company for inspection and repairs.
- 11. Valve on manual priming pump suction was replaced.
During these weeks of testing, there were times when fuel could be drawn from the underground storage tank into the gravity priming tank but not to the diesel. Other times fuel could be drawn to the diesel but not the gravity priming tank. This led to a conclusion that a moving mechanical blockage may exist at the area shown on the attached drawing. Inserting a wire into the line at the diesel back toward the supply tank supported this conclusion when the wire could be inserted no further than the area of the tee shown on the drawing.
Because of the inaccessibility of the fuel lines and new EPA regulations concerning underground tanks, it was decided to replace the entire fuel supply system with above ground tanks for both diesels. Following discussions with insurance company representatives and fire protection engineers, a design was approved and work begun on replacing the fuel supply.
On February 6,1989, the final cor.nections were made from the new fuel supply to the diesel. Testing then was performed on the 6th and 7th of Feb.
On Feb. 8th, the diesel was declcred OPERABLE by the LACBWR Operations Review Committee.
If you have any questions regarding this report, please call us at (608) 689-2331.
Sincerely, DAlRYLAND POWER COOPERATIVE
/
ames W. Taylor General Manager JWT: REC:dh Attachment
1 I
/
's- '. Mr. A.# Btrt Davis
. ^ LAC-12701 Page 3 February 16, 1989 cc: Document Control Desk U. S.. Nuclear Regulatory Commission Washingtoni DC 20555 Mr. Peter B. Erickson, LACBWR Project Manager Division of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 1
li q 1~
.= * - .
i e . eg t a. _
c e k' pc s o $
$a 6L M.
L fg N. 0 f
E o Aa t l
g a t
G(
0c f }
C T ea A t I :
2S AP 1 C 0 Y
f i
o O $
n $
[
u l- -
'f B Y3^ - ,
L
? r '
f u
s -
c L
E d
+c i t F ,e o
d '
,a a L t^
E " ,l S 8>
E I
D W
S P
- l j_
T g
l , ll 1l
